A5039716605- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Particle accelerators and beam dynamics
- Ionosphere and magnetosphere dynamics
- Atomic and Molecular Physics
- Laser-induced spectroscopy and plasma
- Plasma Diagnostics and Applications
- Atomic and Subatomic Physics Research
- Nuclear Materials and Properties
- X-ray Spectroscopy and Fluorescence Analysis
- Laser Design and Applications
- Solar and Space Plasma Dynamics
- Mass Spectrometry Techniques and Applications
- Electron and X-Ray Spectroscopy Techniques
- Crystallography and Radiation Phenomena
- Spacecraft and Cryogenic Technologies
- Electromagnetic Launch and Propulsion Technology
- Muon and positron interactions and applications
- Advancements in Photolithography Techniques
- Thermal properties of materials
- Network Traffic and Congestion Control
Forschungszentrum Jülich
2014-2023
Ghent University
2015-2023
Stadtwerke Jülich (Germany)
2017
Max Planck Institute for Plasma Physics
2014-2016
Max Planck Society
2014-2016
Australian National University
2016
Oak Ridge National Laboratory
2016
Physikalisch-Technische Bundesanstalt
2016
University of Opole
2016
CEA Cadarache
2016
Demonstrating the production of net electricity and operating with a closed fuel-cycle remain unarguably crucial steps towards exploitation fusion power. These are aims demonstration reactor (DEMO) proposed to be built after ITER. This paper briefly describes DEMO design options that being considered in Europe for current conceptual studies as part Roadmap Fusion Electricity Horizon 2020. not intended represent fixed exclusive choices but rather 'proxies' possible plant used identify generic...
This paper describes the progress of DEMO Design Activities in Europe and particularly work done to address critical design integration issues that affect machine configuration performance, plant concept layout selection system technologies. Work continues be primarily focused on a pulsed baseline reactor concept, but number alternative configurations (e.g., double-null divertor snowflake as well ‘flexi’ operates initially an inductively driven regime, with possibility upgraded long-pulse or...
This paper describes the progress of DEMO design and R&D activities in Europe. The focus is on a systems engineering integration approach, which recognized to be essential from an early stage identify address operational challenges, requirements for technology physics R&D. We present some preliminary choices/sensitivity studies explore narrow down space identify/select attractive points. also discuss initial results work being executed EUROfusion Consortium by geographically distributed...
This paper describes the status of pre-conceptual design activities in Europe to advance technical basis a DEMOnstration Fusion Power Plant (DEMO) come operation around middle this century with main aims demonstrating production few hundred MWs net electricity, feasibility closed-tritium fuel cycle, and maintenance systems capable achieving adequate plant availability. is expected benefit as much possible from ITER experience, terms design, licensing, construction. Emphasis on an integrated...
Abstract The optimized superconducting stellarator device Wendelstein 7-X (with major radius , minor and plasma volume) restarted operation after the assembly of a graphite heat shield 10 inertially cooled island divertor modules. This paper reports on results from first high-performance operation. Glow discharge conditioning ECRH discharges in helium turned out to be important for density edge radiation control. Plasma densities with central electron temperatures were routinely achieved...
Abstract Research on magnetic confinement of high-temperature plasmas has the ultimate goal harnessing nuclear fusion for production electricity. Although tokamak 1 is leading toroidal magnetic-confinement concept, it not without shortcomings and community therefore also pursued alternative concepts such as stellarator. Unlike axisymmetric tokamaks, stellarators possess a three-dimensional (3D) field geometry. The availability this additional dimension opens up an extensive configuration...
After completing the main construction phase of Wendelstein 7-X (W7-X) and successfully commissioning device, first plasma operation started at end 2015. Integral start-up using electron cyclotron resonance heating (ECRH) an extensive set diagnostics have been completed, allowing initial physics studies during operational campaign. Both in helium hydrogen, breakdown was easily achieved. Gaining experience with vessel conditioning, discharge lengths could be extended gradually. Eventually,...
DEMO is the name for first stage prototype fusion reactor considered to be next step after ITER towards realizing fusion.For realization of energy especially materials questions pose a significant challenge already today.Heat, particle and neutron loads are problem material lifetime when extrapolating DEMO.For many issues faced advanced solution under discussion or development.In particular components such as wall divertor can benefit from introducing new approaches composites alloys into...
Abstract A large scale program to develop a conceptual design for demonstration fusion power plant (DEMO) has been initiated in Europe. Central elements are the baseline points, which developed by system codes. The assessment of credibility these points is often hampered missing information. main physics and technology content central European codes have published (Kovari et al 2014 Fusion Eng. Des . 89 3054–69, 2016 104 9–20, Reux 2015 Nucl. 55 073011). In addition, this publication...
Abstract Fusion energy research has in the past 40 years focused primarily on tokamak concept, but recent advances plasma theory and computational power have led to renewed interest stellarators. The largest most sophisticated stellarator world, Wendelstein 7-X (W7-X), just started operation, with aim show that earlier weaknesses of this concept been addressed successfully, intrinsic advantages persist, also at parameters approaching those a future fusion plant. Here we first physics...
The plasma diagnostic and control (D&C) system for a future tokamak demonstration fusion reactor (DEMO) will have to provide reliable operation near technical physics limits, while its front-end components be subject strong adverse effects within the nuclear high temperature environment. ongoing developments ITER D&C represent an important starting point progressing towards DEMO. Requirements detailed exploration of are however pushing design using sophisticated methods aiming large spatial...
For several reasons the challenge to keep loads first wall within engineering limits is substantially higher in DEMO compared ITER. Therefore pre-conceptual design development for that currently ongoing Europe needs be based on load estimates are derived employing most recent plasma edge physics knowledge.
The next step in the Wendelstein stellarator line is large superconducting device 7-X, currently under construction Greifswald, Germany. Steady-state operation an intrinsic feature of stellarators, and one key element 7-X mission to demonstrate steady-state plasma conditions relevant for a fusion power plant. device, on hand, requires implementation special technologies, giving rise technical challenges during design, fabrication assembly such device. On other also physics development at...
An initial concept for the plasma diagnostic and control (D&C) system has been developed as part of European studies towards development a demonstration tokamak fusion reactor (DEMO). The main objective is to develop feasible, integrated design DEMO D&C that can provide reliable high performance (electricity output) over extended periods operation. While power maximized when operating near operational limits tokamak, reliability operation typically improves choosing parameters significantly...
The formation and release of particle agglomerates, i.e. debris dusty objects, from plasma facing components the impact such materials on operation in controlled fusion devices has been studied Extrap T2 reversed field pinch TEXTOR tokamak. Several diagnostic techniques, camera observations surface analysis methods were applied for situ ex investigation. results are discussed terms processes that decisive dust transfer: localized power deposition connected with wall locked modes causing...
Abstract The present paper is devoted to a first assessment of the DEMO diagnostics systems and controls in context pulsed steady state reactor design under study Europe. In particular, main arguments treated are: (i) quantities be measured requirements for measurements; (ii) capability diagnostic control technology, determining most urgent gaps, (iii) program strategy research development (R&D) needed fill gaps. Burn control, magnetohydrodynamic stability, basic machine protection...
We present an approach to design in a consistent way stepladder connecting ITER, DEMO and FPP, starting from attractive FPP then locating such that main similarity parameters for the core scenario are constant.The presented suggests how use ITER can be extrapolated with maximum confidence development path plasma scenarios follows our approach, moving low N q typical Q=10 higher values needed steady state.A numerical example is given, indicative of feasibility it backed up by more detailed...
In the present work, role of plasma facing components protection in driving EU-DEMO design will be reviewed, focusing on steady-state and, especially, transients. This work encompasses both first wall (FW) as well divertor. fact, while ITER divertor heat removal technology has been adopted, FW concept shown past years to inadequate for EU-DEMO. is due higher foreseen irradiation damage level, which requires structural materials (like Eurofer) able withstand more than 5 dpa neutron damage....
The first results of the Dynamic Ergodic Divertor in TEXTOR, when operating m/n=3/1 mode configuration, are presented. deeply penetrating external magnetic field perturbation this configuration increases toroidal plasma rotation. Staying below excitation threshold for m/n=2/1 tearing mode, rotation is always direction current, even if projection rotating opposite direction. observed consistent with a radial electric field, generated by an enhanced electron transport ergodic layers near...
Wendelstein 7-X, a superconducting optimized stellarator built in Greifswald/Germany, started its first plasmas with the last closed flux surface (LCFS) defined by 5 uncooled graphite limiters December 2015. At end of 10 weeks long experimental campaign (OP1.1) more than 20 independent diagnostic systems were operation, allowing detailed studies many interesting plasma phenomena. For example, fast neutral gas manometers supported video cameras (including one fast-frame camera frame rates...
The radiative improved (RI) mode is a tokamak regime offering many attractive reactor features. In the article, RI of TEXTOR-94 shown to follow same scaling as linear ohmic confinement and thus identified one most fundamental operational regimes. current understanding derived from experiments modelling conditions necessary for sustaining reviewed, are mechanisms leading L-RI transition. article discusses compatibility high impurity seeding with low central power density burning reactor, well...
With the dynamic ergodic divertor in TEXTOR fundamental effects of coupling external magnetic field perturbations to confined plasma have been studied. The non-linear between (m/n = 12/4) and internal modes 3/1) has investigated. critical perturbation for excitation an m/n 2/1 tearing mode depends not only on magnitude but also direction toroidal angular momentum input by neutral beam injection (NBI). Below threshold this a spin-up observed, which strength field. It is independent both...
Wendelstein 7-X (W7-X) is a large optimized stellarator (B=2.5T, V=30m3) aiming at demonstrating the reactor relevance of stellarators. In 2015 W7-X will begin its first operation phase (OP1.1) with five inertially cooled inboard limiters made graphite. Assuming heat loads can be spread out evenly between limiters, 1 second discharges 2 MW ECRH heating power could run in OP1.1. The expected plasma parameters sufficient to demonstrate readiness installed diagnostics and even physics program....